Thermal conductivity of MOX and MA-bearing MOX

Morimoto, Kyoichi ; Kato, Masato   ; Kihara, Yoshiyuki; Ogasawara, Masahiro*

The Pu-content, O/M ratio and density of MOX fuel of fast reactors are different depending on specifications of fuel. In addition, MOX fuel containing minor actinides has become a candidate for a future nuclear fuel cycle, because it has high proliferation resistance and can reduce environmental burdens by decreasing the amount of MAs in high level radioactive waste. From these points of view, a wide variety of fuel form should be considered on the development of fast reactor fuel. Thermal conductivity of nuclear fuel is one of the most important physical properties for fuel design and performance analysis of fuel rod. In our laboratory, the thermal conductivity measurement has been carried out by using MOX specimens which prepared under various conditions. In this presentation, the various measurement data and the evaluation results of thermal conductivities obtained in our laboratory will be introduced.